Download or read book Autoclave Testing of Zircaloy 2 written by R. A. Thiede and published by . This book was released on 1960 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Autoclave Testing of Zircaloy written by O. Flint and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book In pile autoclave Test of Zircaloy 2 Corrosion in UO2 NO3 2 Solution and of Solution Stability written by R. J. Davis and published by . This book was released on 1962 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Correlation of Autoclave Testing of Zircaloy 4 to In Reactor Corrosion Performance written by RA. Parkins and published by . This book was released on 1994 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: As the service environment for core materials for Pressurized Water Reactors (PWRs) becomes more severe due to increases in water temperature, changes in water chemistry, longer cycle lengths and higher burnups; the corrosion performance of Zircaloy-4 which is used for fuel cladding and structural components becomes more important. The standard three day, 400°C steam autoclave test which has been used to evaluate the uniform corrosion resistance of Zircaloy-4 is no longer sufficient. Some cladding which has given acceptable results in this test has not exhibited satisfactory in-reactor corrosion performance. A series of cladding types for which in-reactor corrosion measurements are available has been subjected to extended autoclave testing in steam at 400 and 415°C. A better correlation to the in-reactor performance is obtained if the 400 °C test is extended to at least 100 days or if the test temperature is raised to 415°C. At 415°C, a test duration of three days is best for evaluating Zircaloy-4 since extended time does not improve the correlation.

Download or read book Preparing Zircaloy 2 for Autoclave Testing written by D. W. Shannon and published by . This book was released on 1959 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Round Robin Tests to Develop a Standard Autoclave Testing Procedure for Zirconium Alloys written by P. E. C. Bryant and published by . This book was released on 1969 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Section I, Subcommittee VIII of ASTM Committee G-1 on Corrosion of Metals conducted two interlaboratory tests, the first with Zircaloy-2, the second with 2.5Nb zirconium, to formulate standard autoclave test procedures for zirconium alloys. In Interlaboratory \1, each laboratory used its own test procedure. The large scatter in data is attributed primarily to differences in autoclave start-up techniques, with minor contributions from variations in pickling time, and residual oxygen remaining in the autoclaves.

Download or read book Corrosion Testing of Zircaloy 2 and Zircaloy 3 written by Stanley Kass and published by . This book was released on 1957 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Development of an Alternative to the Steam Autoclave Test for Zircaloy 2 written by Atomic Energy of Canada Limited and published by . This book was released on 1960 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book IN PILE AUTOCLAVE TEST OF ZIRCALOY 2 CORROSION IN UO2 NO3 2 SOLUTION AND OF SOLUTION STABILITY written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Microstructure of Oxide Layers Formed During Autoclave Testing of Zirconium Alloys written by H-O Andrén and published by . This book was released on 1994 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: The microstructure of oxide layers formed in steam in a 400°C, 10.3-MPa autoclave on different zirconium alloys was studied by transmission electron microscopy. Pre-and post-transition oxide layers on Zircaloy-4 with different heat treatments, and post-transition oxide layers on Zr-0.5Sn-0.53Nb were compared. Special attention was paid to the oxide-metal interface. In Zircaloy-4 with short annealing times and high post-transition corrosion rates, the interface had a disordered structure, and pores were found in the oxide very close to the interface. In Zircaloy-4 with low uniform corrosion rates, the interface consisted of highly ordered, columnar grains. The interface in Zr-0.5Sn-0.53Nb had a different appearance, with an intermediate phase of equiaxed grains between the columnar oxide and the metal. The hydrogen absorption of the zirconium alloys during oxidation was measured by the melt extraction technique on samples oxidized for 63, 147, and 343 days. The Zr-0.5Sn0.53Nb alloy had considerably lower hydrogen absorption than Zircaloy-4.

Download or read book Pressure Testing of Zircaloy Tubing written by L. F. Cochrun and published by . This book was released on 1959 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Controlled Composition Zircaloy 2 Uniform Corrosion Resistance written by CM. Eucken and published by . This book was released on 1991 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: The influence of chemical composition and manufacturing variables on the nodular corrosion resistance (determined by 500°C non-refreshed steam autoclave testing) of controlled composition Zircaloy-2 was reported previously (Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, pp. 334-345.). The present study extends the previous work to include uniform corrosion, which is of interest for cladding tubes and spacer strips.

Download or read book Parametric Study of an Autoclave Test for Nodular Corrosion written by JH. Schemel and published by . This book was released on 1987 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of a steam corrosion autoclave test as a quality control tool for Zircaloy products has been practiced for many years. The most common form of the test is exposure to steam at 672 K, 10.3 MPa (750°F, 1500 psi) for three days. Some years ago it was found that this test did not predict susceptibility to the occurrence nodular corrosion in boiling water reactors (BWR). A number of investigators found that a test at 723 to 773 K would produce nodular corrosion on Zircaloy products and therefore used the test as an index for research work on Zircaloy materials. More recently the test has been proposed as a quality control test on each lot of material. This study of test parameters and interlaboratory variability was undertaken as a necessary part of establishing an ASTM standard for such a test. Temperature of the test was found to be the most significant variable studied, and interlaboratory variation was relatively high when compared with the common 672 K test.

Download or read book Zirconium in the Nuclear Industry written by ASTM Committee B-10 on Reactive and Refractory Metals and Alloys and published by ASTM International. This book was released on 1977 with total page 694 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Download or read book Zirconium in the Nuclear Industry written by Leo F. P. Van Swam and published by ASTM International. This book was released on 1989 with total page 781 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Influence of Chemical Composition on Uniform Corrosion of Zirconium Base Alloys in Autoclave Tests written by CM. Eucken and published by . This book was released on 1989 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The influence of the composition of Zircaloy-type alloys has been evaluated previously with respect to mechanical properties (1973 International Conference Zirconium in the Nuclear Industry, ASTM STP 551) and to nodular corrosion (1985 International ASTM Conference on Zirconium in the Nuclear Industry, ASTM STP 939). The present study extends this previous work to include uniform corrosion, which is of interest for cladding tubes and spacer grids of fuel assemblies. A variety of ingots with compositions both within and outside of the ASTM specification range for Zircaloy-2 and Zircaloy-4 have been tested. The material was fabricated into strips using a conventional fabrication procedure, which incorporated an intermediate beta quench followed by working and annealing in the upper alpha-range. The alloy elements covered the following ranges: tin: 0.2 to 1.7%; iron: 0.05 to 0.53%; chromium: 0.04 to 1.05%; and nickel: 0.003 to 0.046%. In addition, oxygen, carbon, silicon, and phosphorus were varied over the range of standard Zircaloy contents.